Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Ovidiu Balteanu"'
Publikováno v:
Fusion Science and Technology. 76:384-391
In order to ensure the efficient management of radioactive waste in the form of tritiated light water and tritiated heavy water with low tritium and/or deuterium concentration, Institute for Cryoge...
Publikováno v:
Fusion Science and Technology. 76:488-493
The National Research and Development Institute for Cryogenics and Isotopic Technologies (ICSI Rm. Valcea) was established in 1970 as a research entity with the main goal of developing a heavy wate...
Autor:
Felicia Vasut, George Ana, Alina Niculescu, Ciprian Bucur, Ovidiu Balteanu, Marius Zamfirache, Anisia Bornea
Publikováno v:
Fusion Science and Technology. 76:321-326
Whether they are based on fusion (JET, ITER, DEMO) or fission (e.g., CANDU type) or are cooled using molted salts [molten salt reactors (MSRs)], nuclear reactors generate significant amounts of was...
Autor:
Mihai Vijulie, Nicolae Sofilca, Sebastian Brad, Alin Lazar, Ciprian Bucur, Iuliana Stefan, Carmen Moraru, Ovidiu Balteanu
Publikováno v:
Fusion Engineering and Design. 146:1725-1728
The hydrogen isotopes separation plants have special requests related to safety operation and avoidance of radiological fluid leakage and explosion conditions. For the LPCE, part of the ICSI Rm.Valcea “Experimental Pilot Plant for Tritium and Deute
Autor:
Nicolae Bidica, Alina Miu, Ciprian Bucur, Ovidiu Balteanu, Nicolae Sofilca, Gheorghe Ionita, Anisia Bornea, Marius Zamfirache, George Ana, Iuliana Stefan, Felicia Vasut, Ionut Spiridon, Anisoara Oubraham, Alina Niculescu, Liviu Stefan
Publikováno v:
Fusion Engineering and Design. 146:2384-2388
The tritium removal facility (CTRF-Romania) technical project was completed. The applied technology is Liquid Phase Catalytic Exchange combined with Cryogenic Distillation. As this facility will have a lifetime of at least 40 years, research into the
Autor:
Ciprian Bucur, Ovidiu Balteanu, Liviu Stefan, Nicolae Sofilca, Mihai Vijulie, Iuliana Stefan, Carmen Moraru
Publikováno v:
Fusion Engineering and Design. 146:2613-2617
This paper presents control architecture of Liquid Phase Catalytic Exchange (LPCE) process from Pilot Plant for Tritium and Deuterium Separation (PESTD) ICSI Rm. Valcea, as part of plant control and safety strategy. The PESTD control system has been
Autor:
Ioan Stefanescu, Ciprian Bucur, Anisia Bornea, Marius Zamfirache, Nicolae Sofilca, Ovidiu Balteanu
Publikováno v:
Fusion Engineering and Design. 136:1038-1040
One of the main research directions of our institute is represented by the hydrogen isotopes separation process. The research conducted at ICSI during the last 30 years and particularly those related to the Pilot Plant currently being developed at ou
Autor:
Mihai Vijulie, Anisoara Oubraham, Gheorghe Ionita, Ovidiu Balteanu, George Ana, Iuliana Stefan, Nicolae Bidica, Felicia Vasut, Alina Niculescu, Liviu Stefan, Ciprian Bucur, Gheorghe Popescu, Anisia Bornea
Publikováno v:
Fusion Engineering and Design. 161:112044
Liquid Phase Catalytic Exchange (LPCE) as front-end process and Cryogenic Distillation (CD) as back-end process are key processes in detritiation of heavy water used in Cernavoda CANDU-type Nuclear Power Plant (NPP) from Romania as neutron moderator
Autor:
Ciprian Bucur, Nicolae Sofilca, Claudiu Costeanu, Sebastian Brad, Mirela Draghia, Ion Cristescu, Gheorghe Pasca, Ovidiu Balteanu, Carmen Moraru, Iulia Stefan, Mihai Vijulie, Gheorghe Popescu, Robert Daramus, George Ana, Alina Niculescu, Ionut Spiridon, Anisoara Oubraham, Felicia Vasut
Publikováno v:
Fusion Engineering and Design. 106:51-55
Cryogenic distillation (CD) of hydrogen in combination with Liquid Phase Catalytic Exchange (LPCE) or Combined Electrolytic Catalytic Exchange (CECE) process is used for tritium removal/recovery from tritiated water. Tritiated water is being obtained
Autor:
Iuliana Stefan, Mihai Vijulie, Carmen Moraru, Ciprian Bucur, Ovidiu Balteanu, Marius Zamfirache, Nicolae Sofilca, Anisia Bornea, Liviu Stefan
Publikováno v:
Fusion Engineering and Design. 159:111771
Isotopes separation technologies are used in both Tritium Removal Facilities associated with CANDU reactors (to remove tritium from heavy water) and fusion applications (eq. ITER Isotope Separation System) to recover and enrich tritium for further op